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Colin Judge: Testing structural materials in Idaho’s newest hot cell facility
Idaho National Laboratory’s newest facility—the Sample Preparation Laboratory (SPL)—sits across the road from the Hot Fuel Examination Facility (HFEF), which started operating in 1975. SPL will host the first new hot cells at INL’s Materials and Fuels Complex (MFC) in 50 years, giving INL researchers and partners new flexibility to test the structural properties of irradiated materials fresh from the Advanced Test Reactor (ATR) or from a partner’s facility.
Materials meant to withstand extreme conditions in fission or fusion power plants must be tested under similar conditions and pushed past their breaking points so performance and limitations can be understood and improved. Once irradiated, materials samples can be cut down to size in SPL and packaged for testing in other facilities at INL or other national laboratories, commercial labs, or universities. But they can also be subjected to extreme thermal or corrosive conditions and mechanical testing right in SPL, explains Colin Judge, who, as INL’s division director for nuclear materials performance, oversees SPL and other facilities at the MFC.
SPL won’t go “hot” until January 2026, but Judge spoke with NN staff writer Susan Gallier about its capabilities as his team was moving instruments into the new facility.
M. Fujiwara
Fusion Science and Technology | Volume 27 | Number 3 | April 1995 | Pages 58-70
Overview Paper | doi.org/10.13182/FST95-A11947047
Articles are hosted by Taylor and Francis Online.
Recent research has made significant progress for the plasma confinement in helical systems. Experiments have been carried out in W7AS, CHS, ATF, H-E and others. The plasmas, whose electron temperature is around 2–3keV, ion temperature is 1 keV and density is 2–3×1020 m-3, are well confined with the energy confinement time τ E =10–40ms and the stable beta value reaches at < β >> 2% (β (0)=7%)[1]. The obtained scalings for the global energy confinement time such as LHD, GRB(Gyro-Reduced Bohm), L-G(Lackner-Gottardi) scalings are comparable with the tokamak L-mode scaling in the above parameters' range. The improved confinement modes are also explored in helical systems as H mode or the control of plasma profile.
In this paper, firstly present experimental results are reviewed on the confinement, MHD equilibrium/stability beta limit, and secondly the outline of LHD and W7X program is described.
Finally, is discussed the feasibility of helical systems as a fusion reactor, based on the present experimental results.
